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Calibration of Control Drums in a Sub-Critical Assembly

Description: A method of calibrating control drums in a subcritical assembly with a source is given here as an to WANL- TMI- 458 which discusses the measurement of shutdown reactivity in a subcritical core
Date: February 28, 1963
Creator: Rothman, A. B.
Partner: UNT Libraries Government Documents Department
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Control rod studies

Description: This study was undertaken to answer questions asked regarding the required rod stroke for control of modified Tory II-C reactors. All problems described were solved with the Angie code and based on Tory-II-C design problems, RZ 501 and RZ 502, representing hot and cold reactors respectively.
Date: February 28, 1963
Creator: Cole, A.
Partner: UNT Libraries Government Documents Department
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The Diffusion of Lithium in Aluminum

Description: The diffusion of lithium in aluminum was measured at various temperatures with diffusion couples of aluminum-LiAl. The activation energy, E, is 33.3 kcal/mol, and the diffusion factor, Do, is 4.5 cm{sup2}/sec. (auth)
Date: February 28, 1963
Creator: Costas, L. P.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii

Description: In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)
Date: February 28, 1963
Creator: Alsmiller, R. G., Jr.; Alsmiller, F. S. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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A PRELIMINARY EXAMINATION OF THE FORMATION AND UTILIZATION OF TEXTURE AND ANISOTROPY IN ZIRCALOY-2

Description: The anisotropy of mechanicai properties in Zircaloy-2 associated with preferred orientation developed during manufacture has caused many difficulties in the fabrication and utilization of mill products. A preliminary examination of the development and utilization of texture preparatory to an experimental study of anisotropy in Zircaloy-2 tubing is presented. The development of preferred orientation during manufacture of Zircaloy-2 plate, strip, and tubing is qualitatively analyzed in terms of the plastic strain undergone, the modes of deformation operative, the existing anisotropy of flow strengths, and the effects of forming forces of the rolls or dies. The problem of forming structural shapes from anisotropic mill products is discussed, and the utilization of the anisotropy of mechanical properties to ease manufacture and to strengthen structures is considered. (auth)
Date: February 28, 1963
Creator: Picklesimer, M.L.
Partner: UNT Libraries Government Documents Department
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Radiation Survey of the Reactor Vessel Head. Core 1, Seed 3. Test Evaluation

Description: A detailed radiation survey of the Shippingport Reactor vessel head was made, and the magnitude of the radiation in the vicinity of the vessel head after extended power operation and the effect of normal rod motion and scrams on this magnitude are reported. (L.T.W.)
Date: February 28, 1963
Partner: UNT Libraries Government Documents Department
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Scattering of 14-Mev Neutrons From Nitrogen and Oxygen

Description: The differential cross sections for elastic scattering of 14-Mev neutrons from nitrogen and oxygen were measured in the angular range from 17 to 140 deg , using liquid targets and annular ring geometry. Inelastic scattering to the 2.31 and 3.95-Mev levels in N/sup 14/ and to the levels near 6 and 7 Mev in O/sup 16/ was investigated over a more restricted angular range. The 2.31-Mev level in N/sup 14/ was not excited appreciably, in disagreement with previously reported results. For both elements, the elastic scattering cross sections (determined to an accuracy of 10%) were found to be appreciably higher than the optical model predictions by Rjorklund and Fernbach for scatterirg angles larger than 70 deg . The inelastic cross sections measured are, within experimental accuracy, the same as the corresponding (p,p') cross sections. (auth)
Date: February 27, 1963
Creator: Bauer, R. W.; Anderson, J. D. & Christensen, L. J.
Partner: UNT Libraries Government Documents Department
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Development of Batch Formulation Equations for Graphite Fuel Elements

Description: The development of equations used for determination .. starting weights of the individual mix batch constituents is presented. Experimental data resulting from batches compounded in this manner are shown for uranium loading, carbon density, and composite density of as graphitized natural uranium loaded fuel elements.
Date: February 26, 1963
Partner: UNT Libraries Government Documents Department
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Derivation of Linearized, Difference-Differential Equations for Analog Computer Studies of Gas-Flow Oscillations

Description: The basic heat transfer and flow equations applicable to studies of flow oscillations in NERVA engines are first linearized, then expressed as difference-differential approximations, and finally written in a form suitable for analog computer solution. Block diagrams are presented which illustrate on analog procedure for solving the linearized, difference-differential equations.
Date: February 25, 1963
Creator: Stubbs, G.S.
Partner: UNT Libraries Government Documents Department
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Neutron Thermalization Programs for the IBM 7090

Description: A system of six codes is described that permits the solution of a broad class of problems encountered in the study of neutron thermalization, average cross sections, and spectral models. These programs are all compatible with use on MONITOR for the IBM 7090. The Fortran listings are given. (auth)
Date: February 25, 1963
Creator: Preskitt, C.A.; Nephew, E.A. & Tsagaris, M.E.
Partner: UNT Libraries Government Documents Department
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A TRANSFER FUNCTION FOR D.C. OPERATIONAL AMPLIFIERS WITH GENERALIZED EXTERNAL NETWORKS

Description: A transfer function for d-c operational amplifiers with generalized input and feed-back networks is derived by application of network theory. This transfer function, more general than others in common use, applies to three and four-terminal networks. It contains, as a special case, the well-known transfer function for d-c operational amplifiers with two-terminal networks. Examples are given. (auth)
Date: February 25, 1963
Creator: Gossmann, S.R.
Partner: UNT Libraries Government Documents Department
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Waste Management Program: Chemical Processing Department

Description: During the 18-year history of Hanford operations, a high degree of safety has been provided at reasonable cost by the storage of high-activity liquid wastes in underground tanks, by the percolation of low-activity liquid wastes (principally water) through the soil to the ground water, and by the adsorption or filtration of radioactive materials from gaseous effluents prior to their discharge to the atmosphere. Studies of the Hanford area indicate that current practices could be continued almost indefinitely without jeopardizing environmental safety, provided the stored liquid wastes are periodically transferred to new tanks before the existing ones fail. In 1960, a Fission Product Recovery Program was prepared outlining a plan to meet the Atomic Energy Commission`s needs for isolated fission products. Emphasis was placed on developing processes for isolating selected fission products and on providing interim production capability for recovering the fission products of immediate interest. In 1961, development efforts were channeled almost exclusively toward meeting the immediate needs of the Commission for separated strontium-90 and cesium-137. During this time, it became increasingly evident that substantial economies could be realized, both in immediate development and subsequent operating efforts, if the separate fission product recovery and waste management programs were merged. The integration of these programs was therefore effected, as described in the 1962 Waste Management Program. This document describes the current status and goals of the integrated program.
Date: February 25, 1963
Creator: Tomlinson, R. E
Partner: UNT Libraries Government Documents Department
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High Pressure Research at Low Temperatures

Description: Two principle reasons exist for the extension of high pressure research to temperatures near absolute zero. First, the comparison of certain data with theory (such as the pressure-volume relationship) is more meaningful if the effects of thermal vibrations can be ignored. Second, there are phenomena which can be studied only at low temperatures. These include superconductivity, the properties of solid helium and other inert gases, some electronic phenomena, etc.
Date: February 24, 1963
Creator: Swenson, C. A.
Partner: UNT Libraries Government Documents Department
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Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Description: Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: January 1963

Description: This report, for January, 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; financial operations; facilities engineering; research employee relations; weapons manufacturing operation; and power and several maintenance operation.
Date: February 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Shielding Against an 800-Mev Proton Beam

Description: Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)
Date: February 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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PHASE EQUILIBRIA IN THE SYSTEM NaF-UF$sub 4$

Description: No Description Available.
Date: February 21, 1963
Creator: Thoma, R.E.; Insley, H.; Hebert, G.M.; Friedman, H.A. & Weaver, C.F.
Partner: UNT Libraries Government Documents Department
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The Strontium-Strontium Hydride Phase System

Description: Technical report. From Abstract : "The Sr-SrH2 phase diagram was studied by thermal analysis, chemical analysis of equilibrated phases and X-ray diffraction. The maximum solubility of SrH2 in strontium metal is 38 mole % at the peritectic temperature of 880°C. Strontium metal undergoes an allotropic transformation at 555°C and melts at 768°C. A second transformation was found, at about 240°C, in samples containing hydrogen. Strontium hydride was found to have an allotropic transformation at 855°C."
Date: February 20, 1963
Creator: Peterson, D. T. & Colburn, R. P.
Partner: UNT Libraries Government Documents Department
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